Degradation of Steel Containment| ML031250248 |
| Person / Time |
|---|
| Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
|---|
| Issue date: |
12/08/1986 |
|---|
| From: |
Jordan E L NRC/IE |
|---|
| To: |
|
|---|
| References |
|---|
| IN-86-099, NUDOCS 8612050463 |
| Download: ML031250248 (4) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill, Crane |
|---|
Category:NRC Information Notice
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] OR [[:Crane]] </code>. |
SSINS No.: 6835IN 86-99UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF INSPECTION AND ENFORCEMENTWASHINGTON, D.C. 20555December 8, 1986IE INFORMATION NOTICE NO. 86-99: DEGRADATION OF STEEL CONTAINMENTS
Addressees
- All nuclear power reactor facilities holding an operating license or a con-struction permit.
Purpose
- This notice is to provide recipients with current information of a potentiallysignificant safety problem regarding the degradation of a steel containmentresulting from corrosion. It is expected that recipients will review thisinformation for applicability to their facilities and consider actions, asappropriate, to promptly recognize or prevent a similar problem from occurring.However, suggestions contained in this notice do not constitute NRC requirements;therefore, no specific action or written response is required.
Description of Circumstances
- The Oyster Creek Nuclear Generating Station first discovered water in the gapbetween the boiling-water-reactor drywell and the concrete shield in 1980 andbegan investigation of the cause in 1983. It appeared that the collection ofwater varied from a few drops to 2 gallons per minute, depending on whetherthe unit was in operation or an outage for refueling. During the spring andsummer of 1986, the licensee planned work to identify and eliminate this waterproblem. The bellows at the drywell to cavity seal was repaired and a gasketwas replaced, thus stopping the leakage. Since the bellows is located at thetop of the drywell and the region above the bellows is flooded during refueling,it would explain why leakage was high during refueling and low during operation.To determine if the water in the gap had caused damaged to the steel contain-ment, the licensee measured the wall thickness, using an ultrasonic testing (UT)technique at two elevations. The 51-ft level near the drywell seal was sound,but there appeared to be loss of metal on the gap side at the 11-ft 3-in. levelimmediately above the concrete floor. In this area, the gap is packed withsand and contains five equally spaced drain pipes (see attached Figure 1). Atotal of 143 measurements were made at this level and 60 indicated a reductionin thickness of more than 1/4 in. from the drawing thickness of 1.154 in.These readings were found throughout seven of the ten downcomer bays. Thelicensee plans to cut the steel containment and remove about 12 samples toconfirm and evaluate the corrosion damage.8612050463 IN 86-99December 8, 1986 The licensee plans to remove a section of the drain pipe to perform a visualexamination of the outside of the drywell. Wipe samples will be taken fromseveral areas and a chemical analysis will be performed. Sand samples willbe taken adjacent to the core holes and will be analyzed for chemicals, bac-teria, and water composition. Some channels are being cut in the concretefloor that is inside the drywell to provide access for further UT examinationof the containment-sand interface.Discussion:The purpose of the sand is to act as a cushion and allow expansion of thedrywell during operation. The steel containment is in contact with sand inthose areas where corrosion has been detected. The containment material isASTM A-212 Grade B carbon steel plate. The licensee stated that the outsidesurface was protected with a red lead coating from above the drywell down toabout the 10-ft. level, which means that the interface between the lead paintand the unprotected steel was in contact with wet sand. Red lead protectssteel by providing a stable and impenetrable surface, but the steel is sacri-ficial with respect to the lead in dilute, acidic water conditions.It is possible that condensation during initial construction, moisture pickupthrough the drain line during operation, and the leaking bellows wetted thesand, thereby causing corrosion of the containment steel plates. During con-struction, water was seen running down the outside of containment into thesand. The five drain lines, as well as other penetrations in the concreteshield, are open during operation and would allow moist air to enter and riseup the gap and later cool and condense as water. Water also was able to enterthe gap through the holes in the bellows during refueling until repairs weremade.A related matter is discussed in IE Information Notice 86-35, "Fire in Com-pressible Material at Dresden Unit 3," where a large amount of water was usedto extinguish the slowly burning fire between the drywell and the concreteshield. Oyster Creek uses different filler material.The NRC is continuing to obtain and evaluate pertinent information. If spe-cific actions are required, an additional notification will be made.No specific action or written response is required by this informationnotice. If you have any questions about this matter, please contact theRegional Administrator of the appropriate regional office or this office.1dwardLJordan, DirectorDivision f Emergency Preparednessand Engineering ResponseOffice of Inspection and Enforcement
Technical Contact:
Paul Cortland, IE(301) 492-4175
Attachments:
1. Figure 1, Sketch of Possible Degraded Area2. List of Recently Issued IE Information Notices yAttachment 1IN 86-99December 8, 1986 Sketch of Possible Degraded Areas3 IN. ANNULAR SPACEWITH FILLER MATFRtI&pRYWELL1.154 IN. DESIGNTHICKNESSELEVATION 11 FT.ELEVATION 10 FT. 3*CONCRETE. * *OFLOORele4 4 *CONCRETEoo
- 8 Oo* uau°uo0*~ U,^ D ° /4 DRAINAGE CHANNEL 4 4 /A WITH 4 IN. DIA. 00.S SAND FILLED DRAINkh oa PIPE (EVERY OTHERW A <DRYWELL VENT) & 4A U(/ -v,a q0 .,04Figure 1 Attachment 2IN 86-99December 8. 1986LIST OF RECENTLY ISSUEDIE INFORMATION NOTICESInformation -Date ofNotice No. Subject Issue Issued to86-21 Recognition Of American 12/4/86 All power reactorSup. 1 Society Of Mechanical facilities holdingEngineers Accreditation an O or CPProgram For N Stamp Holders86-98 Offsite Medical Services 12/2/86 All power reactorfacilities holdingan OL or CP86-97 Emergency Comaunications 11/28/86 All power reactorSystem facilities holdingan OL or CP and fuelfacilities86-96 Heat Exchanger Fouling Can 11/20/86 All power reactorCause Inadequate Operability facilities holdingOf Service Water Systems an OL or CP86-95 Leak Testing Iodine125 11/14/86 All NRC licenseesSealed Sources In ilx, Inc. authorized to useImaging Devices and Bone Lia1 Inc. imagingMiners Analyzers devices86-94 Hilti Contrete Expansion 11/6/86 All power reactorAnchor Bolts facilities holdingan OL or CP86-93 IE3 85-03 Evaluation Of 11/3/86 All power reactorMotor-Operators Identifies facilities holdingImproper Torque Switch an OL or CPSettings86-82 Failures Of Scram Discharge 11/4/86 All power reactorRev. 1 Volume Vent And Drain Valves facilities holdingan OL or CP86-92 Pressurizer Safety Valve 11/4/86 All PiR facilitiesReliability holding an OL or CPOL
- Construction Permit, ....UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 2055OFFICIAL BUSINESSPENALTY FOR PRIVATE USE. S300FIRST CLASS ALtP0STA1N 6 FEES PAIDUSNACWASI. D.C.PERMI No. 04713357510360n 1 IC01CYlFB11AlNUS CORPLFSLYLE NGABERLICENSING ENGINEER2536 COUNTRYSIOE BLVOCLEARWATER FL 33575
|
|---|
|
| list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986, Topic: Feedwater Heater)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986, Topic: GOTHIC)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Overspeed trip, Overspeed)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib, Loss of Offsite Power)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib, Local Leak Rate Testing, Integrated leak rate test)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986, Topic: Loss of Offsite Power)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986, Topic: Loss of Offsite Power)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl, Potassium iodide)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
... further results |
|---|